W-Cr-Zr systems with different compositions were oxidized in a mixed gas (Ar + 20 vol.% O2) atmosphere at 1000 °C. The power law which was used to describe the oxidation behaviour, indicates that W-11.2wt.%Cr-1.7wt.%Zr has an excellent oxidation behaviour. As analysed from the ten-hour exposure, W-Cr-Zr thin film oxidation shows a self-passivating stage followed by a linear oxidation stage. Furthermore, a study on the addition of zirconium indicates that zirconia particles act as diffusion barriers for the chromium cation diffusion and another function as the nucleation sites for the formation of the initial oxide scale
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
The high-temperature oxidation behavior of ductile Cr-Re alloys contain-ing 32 and 44 a/o (atomic pe...
Self-passivating tungsten based alloys for the first wall armor of future fusion reactors are expect...
International audienceThe oxidation of chromium-coated zirconium-based alloys is studied under steam...
Tungsten is considered the main candidate material for the first-wall in DEMO due to its high meltin...
Tungsten is a prime material candidate for the first wall of a future fusion reactor. In the case of...
The effect of a 1 wt.%Zr on the oxidation behaviour of Fe-15wt.%Cr-4wt.%Al alloy under isothermal co...
Zirconium is one of those few metals which are capable of dissolving relativelylarge quantities of o...
AbstractTungsten is a prime material candidate for the first wall of a future fusion reactor. In the...
International audienceThis study focuses on the oxidation behavior of commercially available HR120 i...
The oxidation of zirconium alloys is one of the most studied processes in the nuclear industry. The ...
International audienceProtective coatings of Zr-based claddings have been proposed for the developme...
Tungsten (W) is currently deemed the main candidate for the plasma-facing armor material of the firs...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
The high-temperature oxidation behavior of ductile Cr-Re alloys contain-ing 32 and 44 a/o (atomic pe...
Self-passivating tungsten based alloys for the first wall armor of future fusion reactors are expect...
International audienceThe oxidation of chromium-coated zirconium-based alloys is studied under steam...
Tungsten is considered the main candidate material for the first-wall in DEMO due to its high meltin...
Tungsten is a prime material candidate for the first wall of a future fusion reactor. In the case of...
The effect of a 1 wt.%Zr on the oxidation behaviour of Fe-15wt.%Cr-4wt.%Al alloy under isothermal co...
Zirconium is one of those few metals which are capable of dissolving relativelylarge quantities of o...
AbstractTungsten is a prime material candidate for the first wall of a future fusion reactor. In the...
International audienceThis study focuses on the oxidation behavior of commercially available HR120 i...
The oxidation of zirconium alloys is one of the most studied processes in the nuclear industry. The ...
International audienceProtective coatings of Zr-based claddings have been proposed for the developme...
Tungsten (W) is currently deemed the main candidate for the plasma-facing armor material of the firs...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
The oxidation of a zirconium based alloy (recrystallised Zircaloy-4) has been studied at 500°C, by t...
The high-temperature oxidation behavior of ductile Cr-Re alloys contain-ing 32 and 44 a/o (atomic pe...